IR 05000295/1993003
| ML20034F038 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 02/18/1993 |
| From: | Louden P, Snell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20034F021 | List: |
| References | |
| 50-295-93-03, 50-295-93-3, 50-304-93-03, 50-304-93-3, NUDOCS 9303020216 | |
| Download: ML20034F038 (7) | |
Text
4
.
U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Reports No. 50-295/93003(DRSS); 50-304/93003(DRSS)
Dockets No. 50-295; 50-304 Licenses No. DPR-39; DPR-48 Licensee:
Commonwealth Edison Company Opus Wost III 1400 Opus Place
Downers Grove, IL 60515 Facility Name:
Zion Nuclear Generating Station, Units 1 and 2 Inspection At:
Zion Station, Zion, Illinois Inspection Conducted:
February J through 5, 1993 Inspector:
CL/l Radiation Specialist Date l
'
Approved By: W
f zA a /D Radiological Controls Section 2 Date Inspection Summary l
Insoection on February 1 throuah 5. 1993 (Recorts No. 50-295/93003(DRSS):
50-304/93003(DRSS))
,
Areas Inspected:
Routine, announced inspection of the licensee's radiation protection (RP) program (Inspection Procedure-(IP) 83750 & 84750) including-changes to the RP department,. training and qualifications,- instrumentation p
calibrations, radioactive source inventories, contamination control, and
ALARA. Additionally, comparative calculations-for gaseous and liquid i
effluents were performed with the NRC PCDOSE computer program.
i.
Results: No violations or deviations of NRC requirements were identified.
The station was in the final stages _of their Unit -2 refueling' outage,.and exposure totals were below established goals and showed improvement compared to the Spring 1992 Unit 1 outage. Comparative calculations performed on gaseous and liquid releases were within established acceptance limits. The station will undergo many-changes in the structure of the RP department (Section 3) but no negative impact is anticipated.
r L
l 9303020216 930219 PDR ADOCK 05000295 G
<
I
.
u
E
..
.,.
DETAILS 1.
' Persons Contacted
.C.pmmonwealth Edison
- T. Broccolo, Superintendent, Site Services
- D. Bump, Supervisor, Station Quality Verification
- K. Dickerson, Regulatory Assurance
_.
,
- 0. Fick, Senior Radiation Protection Technician
- T. Joyce, Zion Station Managen
- S. Kaplan, Supervisor, Regulaton Assurance
- G. Kassner, Operational Lead Health Physicist
- W. Kurth, Superintendent, Production Services
- P. LeBlond, Asst. Superintendent, Operations
.
- R. Mika, Supervisor, Health Physics Services
- R. Palatine, Lead Technical Health Physicist
,
- G. Ponce, Station Quality Control
- L. Simon, Asst. Superintendent, Maintenance
- D. Wozniak, Superintendent, Technical Services The inspector also interviewed other licensee personnel in various departments in the course of the inspection.
i
[Luclear Reaulatory Commission
- J. Smith, Senior Resident inspector
- D. Jones, Reactor Engineer
- Denotes those present at the Exit Meeting on February 5, 1993.
.
2.
. Licensee Action on Previous Insoection Findinas (IP 837501 (Closed) Onen Item (50-295/92007-01(DRSS)):
Station performance with respect to high number of personnel contamination events-(PCEs).
The station recorded 461 PCEs for 1992, well above the projected goal established early in the year. However, PCE occurrence rates for the Unit 2 refueling outage significantly declined. This' decrease was due in part to corrective actions taken by the. station to address ~NRC concerns with the frequency of PCEs during the spring 1992 Unit I outage.
This item is closed.
(Closed) Inspection Followup Item (50-295/92028-01(DRSS):
50-304/92028-01(ORSS)):
Training of personnel on the use of the whole body count software system and performance trending of the whole. body.
counter. This item was initiated due to apparent inadequacies in the knowledge. presented by licensee staff on the execution'of their new
'
software used to analyze data from the whole body counter.
This lack.of familiarity with the system also precluded personnel from performing
-[
..
>
.
U
.
.
.
.
.
.
.
..
-
~
.
'
.
t
.
trending of the system's performance.
Licensee personnel have since received supplemental training and the ability of the staff to trend the-
.
system's performance has improved. This. item is closed.
-
No. violations of NRC requirements were identified.
3.
Oraanizational Chances (IP 83750)
The inspector reviewed pending changes which will occur with respect ~to the organization of the station radiation protection department.
The
,
changes understood at the time of the inspection were as follows:
Health Physics Services Supervisor to Lead Scheduler (Planning)
Operation Lead HP to Health Physics Services Supervisor Technical Lead HP resigning from the company -
ALARA Coordinator resigning from the company
,
HP Scheduler to Industrial Relations Department Turnover briefings were being conducted with the new Health Physics Services Supervisor, and interviews were being conducted for the other vacated positions.
Based on discussions with licensee staff, the-inspector determined that candidates for 'all the positions.to be filled were qualified and no substantial negative impact would be imparted on-the station's radiation protection (RP) program.
,
'
No violations of NRC requirements were identified.
4.
Trainino and Oualifications (IP 83750)
The inspector reviewed training and qualification enhancements to the RP and Chemistry staffs which occurred since the last inspection.
Four radiation protection technicians (RPTs) recently received American National Standards Institute (ANSI) 3.1 experience status,. increasing the RPT staff percentage of ANSI 3.1 qualified individuals _to 68 percent. Additionally, nine RP staff members comprised of RPTs, shift supervisors, ALARA staff, and staff health physicists successfully
completed the National Registry of Radiation Protection Technologists (NRRPT) examination.
This reflects a 90 percent success ratio for those -
members taking the examination.
Licensee representatives met with Region.III personnel on December 23, 1992, to discuss the qualifications of. a chemistry technician who was being considered for promotion to a chemistry supervisor position.
ANSI N18.1-1971, Section 4.3.2, requires four years of experience in-the craft or discipline supervised. The candidate has 3.5 years of
.i experience, including-2 years as a non-licensed operator and-1.5 years as an engineering assistant for operations in chemistry. The
'l
o
.
.
supervisory position reports to the operations lead chemist and is responsible for assigning routine sampling and analysis activities to chemistry technicians, reviewing laboratory data, monitoring chemical additions to plant systems, and reviewing instrument maintenance and quality control. All technical functions are performed in conjunction with degreed technical specialists such as unit chemists, technical and operational lead chemists. The licensee stated that the individual is being considered a trainee in the position for six months until he meets the four year ANSI experience requirement. The question of counting the individual's two years operations experience was reviewed by Region-III.
.
Based on the importance of chemistry parameters in plant operations, the
'
individual's knowledge of plant systems, and NRC positions relative to supervisors assigned to narrow, specific areas of responsibility with small support staffs not being expected to meet the requirements of the standard, Regional management determined that the individual would be acceptable in the supervisory position after the six month training period.
(See HPPOS-172, NUREG/CR-5569, " Health Physics Positions Data Base," May 1992).
.
No violations of NRC requirements were identified.
5.
Contamination Control Proaram (IP 83750)
The station recorded 461 PCEs for 1992. This figure was higher than the anticipated goal at the beginning of the year; however, the station took corrective actions in response to NRC concerns on the adverse trend.
These actions reduced the overall daily rate in which PCEs were occurring.
The station has established a goal of 325 PCEs for 1993 with
<
40 PCEs recorded year to date.
Significant work activities during this period include continuation of the boric acid system modification, reracking the spent fuel pool, and the beginning of a scheduled six month dual unit service water outage.
-
Decontamination efforts were well underway at the time of the inspection to recover many areas contaminated during the Unit 2' outage.
Currently, all the safety injection pump, charging pump, and residual heat removal (RHR) system heat exchanger rooms have been decontaminated.
RHR pump rooms are planned to be decontaminated in the near future.
Overall, good contamination control performance was noted during the Unit 2 outage.
No violations of NRC requirements were identified.
6.
Instrumentation and Eouipment Calibrations. and Radioactive Source Inventories (IP 83750)
The inspector reviewed selected calibration and source check records for various instruments and equipment used to ascertain radiological conditions within the plant.
These devices included R-02, R-02A, E-520, and RM-14 meters; IPM 7 and 8 whole body friskers; and an assortment of continuous air monitoring equipment. All calibration records indicated
,
that the equipment was in proper and current calibration.
Visual t
!
.
4 g
.,b
.
. -
,
.
inspection = of selected samples of each type of instrument indicated that the devices were in good working condition.
-
The inspector. also reviewed radioactive source inventories and records documenting required leak tests. The inventory lists reviewed were in order and leak tests of the sealed sources had been performed within the prescribed timeframe.
No violations of NRC requirements were identified.
7.
tiaintainina Occupational Exposures ALARA (IP 83750)
a.
Unit 2 Refueling 0utage Doses The inspector reviewed the station's performance during the' Unit:2 refueling outage and the incorporation of lessons learned from previous outages.
At the time of the inspection, station exposure totals were 265 person-rem. The projected total for the. entire outage was approximately 275 person-rem which would be below the adjusted outage goal of 300 person-rem.
Details of significant improvements incorporated for this outage are detailed in a
.
previous inspection report (Inspection Reports No.
50-295/92034(DRSS); 50-304/92034(DRSS)).
Exposures for the higher dose job categories were as follows:
74 person -em
'
Inservice' Inspection:
21 person-rem Reactor Head Work':
25 person-rem All of these accumulated doses are below the projected dose-goals established prior to the refuel outage.
b.
Enhancement to Engineering and Construction (ENC) Department-
,
The ENC group had recently enhanced its staff with a full time ALARA coordinator which will work with ENC and the RP department
+
during outage and non-outage times.
Station management indicated
,
that the planned responsibilities of this individual included
!
facilitating work request, radiation work permits, and ALARA'
evaluations for the ENC group and the RP department; providing supplemental training to ENC personnel; and during non-outage times working with'the design engineering group to input ALARA suggestions' during early stages of job package development.-. Many -
other responsibilities were' discussed, but due-to the newness of the position, the station will routinely evaluate which areas will provide the most benefit to the scation. The inspector noted that
-
this enhancement was an improvement for the station ALARA program and addressed an area where the station had previously been
'
.
deficient.
No violations of NRC requirements were identified.
i
. -...
.
-.
.
.
<
~
.
.-
.,
'
..;
8.
Semiannual Effluent Report Data (IP 84750).
The inspector conducted = verification calculations on-four reporting periods for liquid and gaseous effluents contained within recent semiannual effluent reports. The. inspector performed these. calculations -
using the NRC PCDOSE' program which employs equations detailed in
'
Regulatory Guide 1.109. All effluent calculations fell within the-factor of.2 comparative acceptance criteria.
No violations of NRC requirements were identified.
9.
Auxiliary Buildina and Containment Tours H
The inspector made several tours of the radiologically controlled area, including the Unit 2 containment.
The housekeeping of the' Unit 2 containment.was good and the auxiliary building had improved since~the last inspection.
No violations of NRC requirements were identified.
10.
Exit Meetina The scope and findings of the inspection were discussed with licensee representatives (Section 1) at the conclusion of the inspection on-February 5, 1993.
Specific items discussed during the exit meeting are summarized below.
Licensee representatives did not-identify:any documents or processes reviewed during the inspection as proprietary..
Observations of the changes to occur with the organization of the
RP Department.
Comparative results of the gaseous and liquid effluent
calculations performed with PC. DOSE.
The good performance by the station with respect to exposure
totals during the Unit 2 refueling outage.
Closure of the two inspection followup items (Section 2).
i
.
.
i